Zobrazeno 1 - 10
of 26
pro vyhledávání: '"Sang Soon Cho"'
Autor:
Seungpil Kim, Sang Soon Cho
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 10, Pp 4446-4454 (2024)
This paper presents a seismic analysis method that can evaluate a very large number of cases for the free standing dry storage cask by proposing a methodology that has short analysis time as well as accuracy. This study also performed a seismic analy
Externí odkaz:
https://doaj.org/article/0ded2af6e59c4ddcb5300d9f16c2befe
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 7, Pp 2268-2276 (2021)
Spent nuclear fuel, which can degrade during long-term storage, must be transported intact in normal transport conditions. In this regard, many studies, including those involving Multi-Modal Transportation Test (MMTT) campaigns, have been conducted.
Externí odkaz:
https://doaj.org/article/d7f45ff61733406a9778a41aaab99e56
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 11, Pp 3860- (2021)
Externí odkaz:
https://doaj.org/article/b4ce6c5a8d914316b7a7db06012e1682
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 1, Pp 73-80 (2014)
A concrete cask is an option for spent nuclear fuel interim storage. A concrete cask usually consists of a metallic canister which confines the spent nuclear fuel assemblies and a concrete overpack. When the overpack undergoes a missile impact, which
Externí odkaz:
https://doaj.org/article/dc6ebb971294431f8b4d273f8505f699
Publikováno v:
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT). 18:237-245
Metal seals are the main components that establish the containment boundary in bolted casks, which store spent nuclear fuel. These seals are degraded by heat and radiation. In addition, creep occurs when the seals are exposed to intense heat for an e
Publikováno v:
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT). 18:275-289
Publikováno v:
International Journal for Numerical Methods in Engineering. 121:1647-1664
Publikováno v:
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT). 17:167-181
Currently, the development of evaluation technology for vibration and shock load characteristics and spent nuclear fuel structural integrity under normal conditions of transport is being conducted in the Republic of Korea. This is the first such rese
Publikováno v:
International Journal for Numerical Methods in Engineering. 113:277-295
Summary An efficient method for generating the mass matrix inverse of structural dynamic problems is presented, which can be tailored to improve the accuracy of target frequency ranges and/or wave contents. The present method bypasses the use of bior
Publikováno v:
Journal of Magnetics. 20:439-443
A control rod drive mechanism (CRDM) is an electromechanical equipment that provides linear movement for the control rods to control the nuclear reactivity in a nuclear reactor. A rod position indication system (RPIS) detects the control rod’s posi